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Title: Advances in reactor physics education: Visualization of reactor parameters

Abstract

Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)

Authors:
; ;  [1]
  1. Josef Stefan Inst., Jamova cesta 39, SI-1000 Ljubljana (Slovenia)
Publication Date:
Research Org.:
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
OSTI Identifier:
22105679
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 11 refs.
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; CARBON MONOXIDE; COMPUTER CODES; COMPUTER GRAPHICS; DESIGN; EDUCATIONAL TOOLS; FLOW VISUALIZATION; FUEL MANAGEMENT; MODERATORS; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; PARTICLE TRACKS; PWR TYPE REACTORS; REACTOR OPERATION; REACTOR OPERATORS; REACTOR PHYSICS; RESEARCH REACTORS; THREE-DIMENSIONAL CALCULATIONS; TRAINING; TRIGA TYPE REACTORS

Citation Formats

Snoj, L., Kromar, M., and Zerovnik, G. Advances in reactor physics education: Visualization of reactor parameters. United States: N. p., 2012. Web.
Snoj, L., Kromar, M., & Zerovnik, G. Advances in reactor physics education: Visualization of reactor parameters. United States.
Snoj, L., Kromar, M., and Zerovnik, G. 2012. "Advances in reactor physics education: Visualization of reactor parameters". United States. doi:.
@article{osti_22105679,
title = {Advances in reactor physics education: Visualization of reactor parameters},
author = {Snoj, L. and Kromar, M. and Zerovnik, G.},
abstractNote = {Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2012,
month = 7
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

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  • Multi-physics nuclear reactor simulator, which aims to utilize for advanced nuclear engineering education, is being introduced to Nagoya Univ.. The simulator consists of the 'macroscopic' physics simulator and the 'microscopic' physics simulator. The former performs real time simulation of a whole nuclear power plant. The latter is responsible to more detail numerical simulations based on the sophisticated and precise numerical models, while taking into account the plant conditions obtained in the macroscopic physics simulator. Steady-state and kinetics core analyses, fuel mechanical analysis, fluid dynamics analysis, and sub-channel analysis can be carried out in the microscopic physics simulator. Simulation calculations aremore » carried out through dedicated graphical user interface and the simulation results, i.e., spatial and temporal behaviors of major plant parameters are graphically shown. The simulator will provide a bridge between the 'theories' studied with textbooks and the 'physical behaviors' of actual nuclear power plants. (authors)« less
  • A simplified version of the rigorous pole representation of cross sections has been developed to facilitate utilization of the newly released ENDF/B VI resonance data based on the Reich-Moore parameters for reactor applications. The procedure is equivalent to the extraction of the Humblet-Rosenfeld-type parameters and the associated background' term explicitly from the rigorous pole and residue parameters which, in turn, are converted from a given set of the Reich-Moore parameters. The computational efficiency and its amenability to the existing reactor codes are significantly enhanced by the introduction of the pertinent analytic continuation in place of the smooth background' term viamore » the non-linear least square fitting. The method has been successfully applied to all major nuclides examined and the results are presented. 6 refs.« less
  • Advances in graphical user interface (GUI) technology have been accompanied by increasingly sophisticated software applications. This is particularly evident in the area of nuclear fuel management, where the almost complete automation of the reload design process should be realized in the near future. Beyond simple automation, however, the exploitation of visualization capabilities permitted with current technology will allow the reload design engineer to make more informed decisions through broader access to the global picture of parameter interaction. Herein lies the key concept of visualization being incorporated into the System for Integrated Nuclear Fuel Management (SINFUL-MAN) under development at North Carolinamore » State University-the comprehension of multi-dimensionality made possible through the use of such GUI tools as solid rendering, transparency, and cutting planes.« less
  • The individual papers were abstracted separately for the data base. (DG)